ML19320A227

Tech Spec Change Request for Tech Specs 4.2 Re Removal of Surveillance Specimens for Balance of Cycle 1 Operation & Reinsertion Prior to Cycle 2

ML19320A227
Person / Time
Site:	Arkansas Nuclear
Issue date:	05/20/1976
From:	Phillips J ARKANSAS POWER & LIGHT CO.
To:
References
NUDOCS 8004210526
Download: ML19320A227 (2)

Text

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. U.S. NUCU. An HECULA T On"OMM10310N DOCF.CT NUMnt:H u.res ,

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• an_717 NRC DISTRIBUTION rOn PART 50 DOCKET MATERIAL 1

1TO: D.L. Ziemann Fl(OM: Arkansas Power & Ligth Co. DATE OF DOCUMENT Little Rock, Arkansas 5-19-76 )

2.. . J.D. Phillips OATE nECEivEO

_. 5-20-76 '

lDlLETTER , .C NO TO RIZ E O PROP INPUT FORM NUMUEn OF COPIES RECEIVED l DonlGINAL O UNC LASSIF 4 E O ['

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'LC fi'?"981 the following. . . . . . . f 6 ?S$8Ec. Change Request, regarding the remov- l l*

al of the surveillance specimens for the balance of cycle I operation and.requirres their reinser-tion prior t6 Cyc M II.......

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(1 Twix Cy. Received) -

\ ' ACKNOWLEDGED

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I PLANT NAME: Arkansas # 1 . -

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SAFETY FOR ACTION /INFOR?.!ATIO.J Eh?IRO 5AB b-25-/6 l ASSIGMED AD : ,

ASSIG::ED AD :

MRANCH CHIEF : i t.1emann W / 6 BRANCH CHIEF :

FROJECT ::ANAGER: PROJECT MANAGER :

v4C. ASST. :

vi995 LIC. ASST. :

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' NRC PDR  :.mn et rn HETNEMAN l Tmvsco ERNST WI & E (111 SCHRnEnr3 BENAROYA BALT,ARD

' OELD LAIT lLS SPANGLER COSSICK & STAFF ENGINEERIITG IPPCLITO M,IPC MACCARy SITE TET:ll CASE KNIGHT OPERATING REACTORS GADtILL Ik%AUER SIINEIL STELLO STEPP

!LuLEss PAWLICKI HUU!AN OPERATI?!G TECH

! PROJECT MANAGEMEhT REACTOR SAFETY -

-T'ISENI!UT SITE ANALYSIS BOYD ROSS Wi!AO VOLD:ER P. COLLINS NCVAK _

WAER BUNCH ll0USTON '- - h- COLLINS R0_SZTOCZY *CIR))R!CI:R 1lETE,RSON Cl!ECK -

M IMES KREGER MM_LTZ IIELTEMMS AT & I i

SITE SAFETY & UNVIRC SKOVHOLT SAT.TZMAN .

A?IALYSIS lillTI5E'!U',

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l 15-261 lten Component Excention 6.4 Rolting 20 l

Not Applicab]

6.6 Integrally h'elded Not Applicabl '

i Yalve Supports 4.2.3

%e structural integrity of the reactor coolant system bout 'I shall be r,aintained at the level required by the original tance

( andards throughout the life of the station. Any e-j as a result of the tests outlined in Tabic IS-261 of Sectic i j of the code, that defects have developed or grown, shall bt investigated. i 4.2.4-To assure the structural integrity of the reactor internals l t out the life of the unit, the two sets of nain internals bc I (connecting the core barrel to the core support shield and '

lower grid cylinder) shall remain in place and under tensio will be verified by visual inspection to determine that the bolt loc. king caps remain in place. All locking caps will b cd after hot functional testing and whenever the internals renoved from the vessel during a refueling or naintenance a The coteshutdown.

refueling barrel to core support shield caps will be inspect 4.2.5 p Sufficient records of each inspection shall be kept to allo, comparison and evaluation of future inspections, a

4.2.6 y Cowpicte surface and volte::ctric examination of the reactor t ~

p cp flywheels will be conducted coincident with refueling 1 naintenance shutdowns such that within a 10 year period aft:

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up all four reactor coolant ptmp flywheels will be exanined.

i 4.2.7 Reactor vessel spccinens shall be removed and examined, to d eine changes in caterial properties, at specinen exposures (

-l equivalent to 3, 9.5,16 and 22.5 Effective Full Power Years of operation.

j his withdrawal schedule may be modified to c with those refueling outages or plant shutdowns, when the re head is renoved, nost closely approaching the withdrawal sch Results of these exaninations shall be used to update Techni l Specification 3.1.2. Specirsens not subjected to destrt.ctivo testing after the first 0.93 EFpY of Cycle 1 asy be removed stored during the renainder of Cycle 1, but shall be re-inst.

y prior to (.'ycle 2.

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%e surveillance ASMI: progran has been developed to couply with Section XI

• l Boller Coolant Systens. 1971. includingand Pressurc Vessel Code Inservice Inspection of Nuclear Rf 1971 Winter Addenda Edition p l f' De ntu:ber of reactor vessel specimens and the frequencies for renovin; and testing these spccicens are provided to assure compliance with the l requirements of Appendix 11 to 10CFR Part 50.

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